Title of article
Preliminary test for reprocessing technology development of tritium breeders
Author/Authors
Hoshino، نويسنده , , Tsuyoshi and Tsuchiya، نويسنده , , Kunihiko and Hayashi، نويسنده , , Kimio and Nakamura، نويسنده , , Mutsumi and Terunuma، نويسنده , , Hitoshi and Tatenuma، نويسنده , , Katsuyoshi، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2009
Pages
4
From page
1107
To page
1110
Abstract
In order to develop the reprocessing technology of lithium ceramics (Li2TiO3, CaO-doped Li2TiO3, Li4SiO4 and Li2O) as tritium breeder materials for fusion reactors, the dissolution methods of lithium ceramics to recover 6Li resource and the purification method of their lithium solutions to remove irradiated impurities (60Co) were investigated. In the present work, the dissolving rates of lithium from each lithium ceramic powder using chemical aqueous reagents such as HNO3, H2O2 and citric acid (C6H8O7 · H2O) were higher than 90%. Further the decontamination rate of 60Co added into the solutions dissolving lithium ceramics was higher than 97% using the activated carbon impregnated with 8-hydroxyquinolinol as chelate agent.
Journal title
Journal of Nuclear Materials
Serial Year
2009
Journal title
Journal of Nuclear Materials
Record number
1366442
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